U-Mo合金に関する研究

Some studies on a the uranium-molybdebumm alloy

川崎 正之; 長崎 隆吉; 板垣 元雄*; 竹村 達也*

Kawasaki, Masayuki; Nagasaki, R.; Itagaki, M.*; Takemura, Michio*

None

U-Mo alloy is of interest as power-reactor fuel. The purpose of this work was to study the characteristic behavior of the alloy when subjected to certain heat treatments as well as to get fundamental informations concerning its general properties. The specimens were made by vacuum induction melting and were rolled at 600 and 900C. In the heat treatment tests, the phase changes by quenching from various high temperature phases, the effects of quenching rate from gamma phase range, and Ms temperature for 1.30% Mo alloy were the subjects discussed. Thermal cycling test revealed that greater improvement was obtained by gamma quenching followed by alpha annealing for the rolled rods with Mo content ranging from 0.5 to 9.0%. Oxidation test in air at 300, 400 and 500C had shown that the rate constant of oxidation decreased with increasing Mo contents in the lower Mo range, but it increased as Mo contents became higher. The same tendency was observed on the corrosion test in hot water. The minimum weight loss in 350C hot water could be obtained at 12w/o Mo.